This report summarizes the results of the seventh and last of a series of tests completed in the A-11 test program during the Contract Year 1964

In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)

Possible experiments that could be performed at the Brookhaven alternating gradient synchrotron using highenergy deuterons and heavier nuclei are reviewed. Particular attention is given to production of high-energy neutrons by stripping. A brief analysis of changes needed to accelerate heavier nuclei reveals such modifications would not be prohibitive. (D.C.W.)

This report talks about Aerospace Nuclear Safety.

The destruction of a full scale mockup ROVER/NERVA propulsion engine· was performed under the direction of the joint AEC/NASA Space Nuclear Propulsion Office. The instrumentation was developed and installed by Aberdeen Proving Ground and Sandia Corporation. The data collected included information about the destruct debris velocity, size, weight, and spacial distribution. These data are a satisfactory source term for the computer analysis of the ROVER/NERVA Program safety.

A summary of the progress on development of the ALGOL compiler for the Control Data Corporation 1604 Computer is presented. This computer is based on machine-independent specifications developed at ORNL. A brief description of the structure of the compiler is included along with discussions concerning language restrictions, the hardware language representation, and the required equipment configuration. An example illustrates the generated program instructions. (auth)

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Research and development progress is reported on analytical instrumentation, chemical analysis of advanced reactor fuels, analytical studies of molten-salt systems, special research problems, reactor projects, effects of radiation on analytical methods, x-ray and spectrochemical analyses, spectroscopy, optical and electron microscopy, nuclear and radiochemical analyses, inorganic preparations, organic preparations, and analytical development. Service analyses are also described. Separate abstracts were prepared for each topic. (M.C.G.)

Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.

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Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.

An aggressive attack in the management of malignant disease by chemotherapeutic means has been hampered by toxic effects of these agents on bone marrow, gastrointestinal tract, and skin.

The Brookhaven Bubble Chamber Group is developing a Hough-Powell fast analysis system (HPD)1 for bubble chamber photographs. High precision measurements are made with a computer controlled flying spot digitizer. We are currently testing the track selection programs for the system. We have just completed a study of a method for automatic bubble density measurements.

The equations and procedures of the PTD-1 program for obtaining the surface temperature distribution, the gas bulk temperature, and the pressure distribution for any of the 234 channels in the EGCR are developed. The program, in FORTRAN for the IBM 7090, is designed for any arbitrary power distribution yielding a constant gas outiet temperature or a given maximum surface temperature and includes the effects of thermal radiation on surface and bulk gas temperatures. The flow sheet and some results are included. (auth)

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A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in length and 2.26 ia. in diameter with specimen power generation up to 150 kw. The maximum coolant temperature at the specimen outlet is set at 1500 deg F. The loop system includes the in-reactor section, the machinery, the control system, and the specimen-handling apparatus. Salient features of the re-ertrant system include an aluminum pressure wall in the in-reactor section, static gas insulation between the reactor coolant and the circulating loop gas, and a controllable rate of heat exchange between the specimen inlet- and specimen outlet-gas channels in sections of concentric countedlow piping. The three blowers in the system feature grease-lubricated bearings and water cooling. The complete system was tested out of pile and is now installed in …

The stated objective of the SNAP-50 reactor and primary system development program is the design, fabrication, development and test operation of a series of reactors and associated equipment leading to a fully qualified and accepted SNAP-50 flight reactor and primary system.

Concentrations of fission products in the fuel and in the coolant stream of a generalized reactor power plant employing unclad fuel material were calculated using actual fission-product chains and wide ranges of assumed values of escape rate from the fuel and removal rate from the coolant stream. The calculations were made on an IBM 704 digital computer. Some typical results are displayed in the form of graphs to illustrate the effects of the variables. As data on escape rates from fuel and removal rates from coolant become available, the tables and graphs developed by this study can be used to estimate the fissionproduct concentration in the coolant stream, which would in turn furnish a basis for determining the degree of coolant purification required to maintain the circulating activity below a given level. (auth)

On April 16, 1962, the fuel charge in overbore tube 3062-C sustained a failure, and upon examination after discharge was found to contain three split failures and three ``worm tracked`` elements (depression in the aluminum cladding apparently the result of uranium cleavage and subsequent yielding of the cladding). These failures occurred approximately ten days following a period of reactor neutron flux cycling, and during a second cycle at C Reactor. In addition to the failures, a total of 17 elements, from nine separate fuel charges, contained worm tracks. Four of these elements were sent to Radiometallurgy Laboratory for destructive examination, to determine the mechanism of the suspected uranium cleavage.

The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element are presented. The tests were performed to investigate the possibility of damage to such long thermal-time-constant fuel rods when subjected to short-period power excursions, and to test the effectiveness of an instrumentation technique for measurement of UO/sub 2/ fuel temperatures within the rods. In an initial series of power excursion tests, in which the range of reactor periods was from approximately 1 sec to 7.5 msec, simultaneous measurements were made of the transient temperature at the center of the fuel rod and at the outer cladding surface. Fuel rod rupture occurred during the exponential rise of the 7.5-msec excursion. Similar short-period tests performed on a second fuel rod contain ing no internal thermocouples did not result in cladding failure, supporting the postulation that rupture of the first rod was caused by waterlogging of the UO/sub 2/ as a result of the cladding penetrations made for installation of the internal thermocouples. Calculations of the transient temperature distribution in the fuel rod were made, and the results are found to be in good agreement with the experimental data obtained on the central-UO/sub 2/ and cladding-surface …

Calculations are made to determine the safe steadystate power operating limits of the Spert III reactor from the viewpoint of fuel plate burnout. A computer program is developed for the IBM 704 to aid in these calculations. The Bettis design departure from nucleate boiling (DNB) equation is used in conjunction with the LeTourneau and Grimble method of hot channel'' analysis in the development of the calculations. For cases where DNB occurs in the bulk boiling region, a modified Martinelli-Nelson twophase flow correlation and some experimental singlephase pressure drop data are employed. DNB for a typical operating condition of 550 deg F inlet temperature and 2500 psig is computed to check the code. The results of the sample calculation show that at a steady- state power level of 60 Mw (maximum design power) the minimum flow rate required to prevent DNB is approximately 8000 gpm. (auth)

Equations based on kinetic theory relate the contamination of refractory metals in vacuum to the appropriate variables. Several examples are given for which the allowable system pressures are calculated. The examples illustrate the effect of varying several parameters. The importance of the sticking factor for active gases on hot refractory metals and its effect on the system design are discussed. The data for estimating the sticking factor for O/sub 2/ on Nb are given, along with some estimated values. Experimental data on the composition and rates of outgassing of ultrahigh-vacuum systems and their importance in system design are discussed. Several methods of reducing contamination rates and the relative ease and effectiveness of these methods are presented. It was concluded that tests of 1000 hr or longer will probably require system pressures of between 10/sup -9/ and 10/sup -6/ torr, the particular pressure depending upon the residual gas composition, test duration, allowable contamination level, and the other variables discussed. Since the most important source of contamination in a properly designed ultrahigh-vacuum system is the outgassing process, bakeable systems should be designed to operate with walls as cool as practical, and to have a minimum of surface area and outgassing materials inside. …

Cobalt irradiations were completed in two C-Reactor overbore tubes in support of Mission and Program investigations of isotope production. Tubes 1459 and 464 were each charged with approximately 4015 grams of cobalt in strips similar to BNL pieces described in a separate report. After discharge, the strips were placed in an underwater calorimeter to determine the heat contribution from isotopic decay, thereby allowing an assay of cobalt-60 concentrations. The cobalt-60 produced in tube 1464-C was retained by Douglas United Nuclear for source material in an underwater gamma irradiator at KE-Reactor; the remaining cobalt, from tube 1459-C, was shipped to Battelle-Northwest for further experiments and applications. A total of 396,400 Ci of cobalt-60 was produced in tube 1459-C and 272,700 Ci in tube 1464-C during the irradiations. Production in tube 1459-C occurred at the rate of 0.637 Ci/gm per 100 MWd/T of adjacent tube power; production in tube 1464-C occurred at the rate of 0.670 Ci/gm per 100 MWd/T of adjacent tube power. The total irradiation time was 880.813 full power days for tube 1459-C and 569.010 full power days for tube 1464-C.

The utilization of physical and chemical processes to reduce the rate of vapor loss of thermionic emitters composed of mixed carbides of U and Zr in order to increase the permissible operating temperature is being studied. Preliminary, qualitative results obtained from study of physical redeposition processes showed that increasing the collector temperature may markedly reduce the rate of weight loss from a UC emitter operating at 2053 deg K. The requisite experimental equipment for studies of chemical transport processes was designed and constructed. Experiments will proceed through both a physical chemistry approach to an understanding of the transport processes and a technique to evaluate the efficacy of possible combinations of chemical species by monitoring the electron emission from diodes containing such mixtures. (auth)